ML18038B514
| ML18038B514 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/02/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18038B515 | List: |
| References | |
| DPR-33-A-226, DPR-52-A-241, DPR-68-A-200 NUDOCS 9511080319 | |
| Download: ML18038B514 (17) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 T NNESSEE VA Y AU ORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1
AMENDM NT TO FACILITY OPERATING LICENSE Amendment No.
226 License No. DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 30,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
95ii0803i9 95ii02 PDR ADQCK 05000259 P
2.
Accordingly, Facility Operating License No. DPR-33, page 5, paragraph 2.C.(13), is hereby amended to reflect issuance of the staff safety evaluation of the Appendix R Safe Shutdown Program; to read as follows:
(13)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection=
Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,
- 1988, March 6,
- 1991, March 31,
- 1993, November 2, 1995 and Supplement dated November 3, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of >he Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g~&..ll Frederick J.
HebJ o, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Page 5 of License DPR-33 Date of Issuance:
November 2, 1995 Page 5 is attached for convenience, for the composite license to reflect this change.
(11)
The licensee shall fully implement aad maj~tain in effect provisions of the Commission-approved physical security>
guard training and qualification, and eafcguards contingency plans including amcndmcnts made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 aad 27822) and to the authority of 10 CFR 50'0 and 10 CFR 50 '4(p) ~
The plane, <<hich contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Brome Ferry Physical Security Plan", <<ith revisions submitted through May 24, 1988; "Browne Ferry Security Persorinel Training and Qualification Plaa", with revisions submitted 'through hpril 16, 1987; and*"Browne Ferry Safeguards Contingency Plan", <<ith revisions submitted through June 27, 1986.
Changes made ia accordance with 10 CFR 73'5 shall be implcmcated in accordance <<ith the schedule set forth therein.
(12)
The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside thc security fence, as presently located, but inside thc site exclusion area.
The total amount of low-level waste to be stored shall not exceed 1320 curies of total activity.
This authorization cxpiree two years from the effective date of this amendment and is subject, to all the conditions and restrictions in TVh's applicatioa dated January 21, 1980.
(13)
Browne Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BEN i' approved in the SEs dated December 8. 1988, March 6, 1991, March 31, 1993, Hoveaher 2, 1995 and ~plemmt dated November 3, 1989 subject to the following provisions The licensee may make changes to the approved fire protection program without prior approval of the Comniseion only if those changes would not adversely affect the ability to achicvc and maintaia safe shutdown in the event of a fire.
D.
This amended license is effective as of the date of issuance aad shall expire midnight on December 20, 2013
'OR THE ATOMIC ENERGY COMMISSION l~
- h. Giambueso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
DEC 20 1973 BFN Unit 1 Amendments SS, 78, fS7 f87. TN,226
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 ROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
241 License No. DPR-52 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 30,
- 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by.
this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.
DPR-52 is hereby amended to read as follows:
3.
(2)
Technical S ecifications
'The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 241, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
Also, page 6, paragraph 2.C.(14) of the license is amended to reflect issuance of the staff safety evaluation of the Appendix R Safe Shutdown Frogram; to read as follows:
(14)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,
- 1988, March 6,
- 1991, March 31,
- 1993, November 2, 1995 and Supplement dated November 3, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J.
Heb n, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation.
Attachment:
1.
Page 6 of License DPR-52 2.
Changes to the Technical Specifications Date oK Issuance:
november 2, 1995
- Page 6 is attached for convenience, for the composite license to reflect this change.
(12)
The licensee is authorised to temporarily store lov level radioactive vaste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site exclusion area.
The total amount of lov-level vaste to be stored shall not exceed 1320 curios of total activity This authorisation expireo tvo'years from the effective date of this amendment and is sub)ect to all the conditions and restrictions in TVA's application date'd January 21'980 ~
(13)
Commission Order dated March 25'983 is modified aa follovs:
in Attachment 1, for item II.F.l.l and II.F.1.2 change "12/31/84" to "Prior to startup in Cycle 6."
(14)
Brovns Ferry nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BPK as approved in the SEs dated December 8, 1988, March 6, 1991, March 31, 1993, November 2, 1995 and Supp1ement dated November 3, 1989 subject to the Sollmring provision:
The licensee may aake changes to the approved fire protection program vithout prior approval of the Coraission only if those changes vould not adversely affect the ability to achieve and maintain safe shutdovn in the event of a fire.
D.
This amended license ia effective as of the date of issuance and shall expire midnight on June 28, 2014.
FOR THE ATONIC ENERGY COSGSSIO1 S/
A. Giambusso, Deputy Director for Reactor Pro)acts Directorate of Licensing httachment:
Appendices A tc B - Tedmical Specifications Date of Issuance:
JUK 28, 1974 BFÃ Unit 2
~ggNSt Ne. 844 241
TTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.
The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
- Overleaf page is provided to maintain document completeness.
REMOVE 1.0-12a 1.0-12.b INSERT 1.0-12a 1.0-12.b*
A
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f DEFINITIONS Cont'd NN.
A endix R Safe Shutdown Pro ram BFN has developed an Appendix R Safe Shutdown Program.
This Program is to ensure that the equipment required by the Appendix R Safe Shutdown Analysis is maintained and demonstrated functional as follows:
1.
The functional requirements of the Safe Shutdown systems and equipment, as well as appropriate compensatory measures should these systems/components be unable to perform their intended function are outlined in Section III of the Program.
2.
Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.
00.
CORE OPERATING LIMITS REPORT COLR The COLR is the unit-specific document that provides the core operating limits for the current operating cycle.
These cycle-specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.9.1.7.
Plant operation within these limits is addressed in individual specifications.
PP.
Limitin Control Rod Pattern A limiting control rod pattern shall be a pattern which results in the core being on a thermal limit, i.e. operating on a limiting value for APLHGR, LHGR~ or HCPR.
BFN Unit 2 1.0-12a Anendnent iso.
241
THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 2 1.0-12')
NENDMENT NO. 1 9 2
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 205554001 TENNESSEE VALL AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 M NDM NT 0 FACILITY OPERATING LICENSE Amendment No.
200 License No. DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 30,
- 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No.
DPR-68 is hereby amended to read as follows:
3.
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 200, are hereby incorporated in the license.
The licensee shall oper ate the facility in accordance with the Technical Specifications.
Also, page 4, paragraph 2.C.(7) of the license is amended to reflect issuance of the staff safety evaluation of the Appendix R Safe Shutdown Program; to read as follows:
(7)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,
- 1988, March 6,
- 1991, March 31,
- 1993, November 2, 1995 and Supplement dated November 3, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g Cj1 Frederick J.
Heb on, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
1.
Page 4 of License DPR-68 2.
Changes to the Technical Specifications Date of Issuance:
November 2, 1995
- Page 4 is attached for convenience, for the composite license to reflect this change.
(4) Thc licensee shall maintain in effect and fully implement all provisions of thc Coamissioa approved physical security plan including amendments made pursuant. to the authority of-10 CFR 50.54(p).
The approved plan, which contains information protected under 10 CFR 73.21, is entitled "Browas Ferry Nuclear Plant Physical Security Plan," dated May 15, 1982 (TVh letter dated June 11, 1982) aad revisions submitted by TVA letters dated August 31, 1982 aad October 19, 1982.
(5) The licensee shall follow all provisions of the NRC ayyroved Guard Training & Qualification Plan, includiag amcndmcnts aad changes made pursuant to 10 CFR 50.54(p).
The ayyroved Guard Trainiag &
Qualification Plan is identified as "Browas Ferry Nuclear Povcr Station Guard Training & Qualification Plan," dated hugust 17, 1979, as revised by pages dated January 24, 1980, May 21, 1980, October 1,
- 1980, and March 9, 1981 and as may subsequently bc revised in accordance vith 10 CFR 50.54(y).
The Guard Training & Qualification Plan shall bc followed, in accordance vith 10 CFR 73.55(b),
60 days after the date of thia amendment.
(6) The licensee shall fully imylement and maintain in effect all provisions of the Couaissioa-approved physical security, guard training and qualification, and safcguards contingency plans including amcndmcnts made yursuant to provisions of the Miscellaneous hmendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, vhich coatain Safcguards Information protected under 10 CFR 73.21, are entitled:
"Browns Ferry Physical Security Plan", vith revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through hpril 16, 1987; and "Brovns Ferry Safcguards Contingency Plan", vith revisions submitted through Junc 27, 1986.
Changes made in accordance vith 10 CFR 73.55 shall be implemented in accordance vith thc schedule sct forth therein.
(7)
Brovns Ferry Nuclear Plant shall implement and maintain in effect all provisioas of thc approved Fire Protection Program as dcscribcd in the Final Safety haalysis Report for BFK as approved in the SEs dated December 8, 1988, March 6, 1991, March 31, 1993, november 2, 1995 and Supplement dated November 3, 1989 subject to the following provision:
The licensee may aake changes to the apyroved fire protection program vithout prior approval of thc Commission only if those changes vould not adversely affect the ability to achieve and maintain safe shutdovn in the event of a fire.
BFH Unit 3 amxnmm
~m /KH, 200
TTACHM N 0
L C
NSE AMENDM T NO. ~
FACILIT OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.
The revised page is identified by the captioned amendment number and contains marginal lines indicating the areas of change.
- Overleaf page is provided to maintain document completeness.
'~RMOVE 1.0-12a
- 1.0-12b INSERT 1.0-12a 1.0-12b*
1.0 DEFINITIONS Cont'd NN.
A endix R Safe Shutdown Pro ram BFN has developed an Appendix R Safe Shutdown Program.
This program is to ensure that the equipment required by Appendix R Safe Shutdown Analysis is maintained and demonstrated functional as follows:
1.
The functional requirements of the Safe Shutdown Systems and equipment, as well as appropriate compensatory measures
'should these systems/components be unable to perform their intended function are outlined in Section III of the program.
2.
Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.
00.
CORE OPERATING LIMITS REPORT COLR The COLR is the unit-specific document that provides the core operating limits for the current operating cycle.
These cycle-specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.9.1.7.
Plant operation within these limits is addressed in individual specifications.
PP.
LIMITING CONTROL ROD PATTERN A LIMITING CONTROL ROD PATTERN shall
)
be a pattern which results in the core being on a thermal limit, i.e. operating on a limiting value for APLHGR, LHGR, or MCPR.
BFN Unit 3 1.0-12a Anendnent Ho.
200
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~
THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 3 1.0-12b AMENDMENTNO. I V 0